monticello nuclear generating plant - 2019 refueling ... · xcel energy® resp o ns i b le b v nat...

Xcel Energy® RESP O NS I B LE B V NAT U RE®

August 9, 2019

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Lie

Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22

2807 West County Road 75 Monticello, MN 55362

L-MT-19-028 10 CFR 50.55a(g)

License Conditions 2.C.(15)(f) and (g)

2019 Refueling Outage 90-Day lnservice Inspection (ISi) Summary Report; Second Steam Dryer Inspection Summary

Pursuant to 10 CFR 50.55a(g), Northern States Power Company - a Minnesota corporation (NSPM), doing business as Xcel Energy, hereby submits the enclosed lnservice Inspection (ISi) Summary Report and Form OAR-1 "Owner's Activity Report" (Enclosure 1) for the Monticello Nuclear Generating Plant (MNGP).

The Owner's Activity Report has been prepared in accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code, Section XI Code Case N-532-5, "Alternative Requirements to Repair and Replacement Documentation Requirements and lnservice Summary Report Preparation and Submissions as Required by IWA-400.0 and IWA-6000, Section XI, Division 1." This code case is an alternative to the requirements of ASME Boiler and Pressure Vessel Code, Section XI, Articles IWA-4000 and IWA-6000, as authorized by the U. S. Nuclear Regulatory Commission (NRC) through Regulatory Guide 1.147, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision 18, March 2017.

The Owner's Activity Report is included in the enclosure and provides an overview of inservice examination results and repair/replacement activities performed during Cycle 29, including the 2019 Refueling Outage (1 R29). The activities are applicable to the Fifth 10-year ISi Interval that began on September 1, 2012 and the Second 10-year IWE Interval that began on September 9, 2009.

Included with the OAR-1 form are Tables 1 and 2 entitled "Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service" and "Abstract of Repair/ Replacement Activities Required for Continued Service", respectively, in accordance with

Document Control Desk

ASME Code Case N-532-5 for Cycle 29. Also included is Cycle 23 ISi Summary Report Supplemental Information.

The second steam dryer visual inspection was conducted during the 2019 Refueling Outage (RFO) to meet MNGP Renewed Facility Operating License DPR-22, License Conditions 2.C.(15)(f) and (g), that are stated below:

Condition f: During the first two scheduled refueling outages after reaching EPU [Extended Power Uprate] conditions, a visual inspection shall be conducted of all accessible, susceptible locations of the steam dryer in accordance with the inspection guidelines provided to the NRG.

Condition g: The results of the visual inspections of the steam dryer shall be reported to the NRG staff within 90 days following startup from the respective refueling outage.

The MNGP steam dryer visual inspection results from RFO-29 are provided for the second complete operating cycle at full EPU conditions within the Enclosure 2 titled "IWI Steam Dryer Inspection Results RFO29".

Summary of Commitments

This letter makes no new commitments and no revisions to existing commitments.

~1t.~ Christopher R. Church Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota

Enclosures (2)

cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC

ENCLOSURE 1

Monticello Nuclear Generating Plant

Owner's Activity Report

Form OAR-1

Xcel Energy-

Xcel Energy, Inc. Northern States Power Co. - Minnesota

414 Nicollet Mall Minneapolis, MN 55401

INSERVICE INSPECTION

SUMMARY REPORT

Monticello Nuclear Generating Plant Unit 1 2807 West County Road 75

Monticello, MN 55362

Commercial Service Date: June 30, 1971

Cycle No. 29 Refueling Outage

Outage Dates: April 13, 2019 to May 13, 2019

lnservice Inspection: Interval 5 (September 1, 2012 - May 31, 2022) Period 2 (September 1, 2015 -August 31, 2019)

Containment (IWE) Inspection: ~nterval 2 (September 9, 2009 - September 8, 2019) Period 3 (September 9, 2015 - September 8, 2019)

(per IWA-2430( d)(3))

Report Date: August 7, 2019

Prepared By:

Reviewed By:

Approved By:

ANII:

Richard Deopere Program Engineer, ISi Program Owner

.... I itt~ /a1<(l

1 'Tom Jones Program Engineer, Site NDE Levellll

;'.'/ p ("? ,~•✓ /'" ,m~~"'>, ,,,,,,,-"

Patil Young Manager, Program Engineering

Kurt Suleski The Hartford Steam Boiler Inspection and Insurance Company

Monticello Nuclear Generating Plant Inservice Inspection

1.

2.

3.

4.

TABLE OF CONTENTS

SECTIONS

Summary

Form OAR-1, Owner's Activity Report for Cycle 29

Table 1, Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service

Table 2, Abstract of Repair/Replacement Activities Required for Continued Service

Cycle 29 Summary Report 2019 Refueling Outage

PAGES

1

1

1

1

5. Cycle 23 ISI Summary Report Supplemental Information 7


SECTION 1. SUMMARY


Page 1 of 1

In accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI and approved alternative requirements of Code Case N-532-5 1

, this report provides the following:

• Form OAR-1, Owner's Activity Report • Table 1, Items with Flaws or Relevant Conditions That Required Evaluation

for Continued Service • Table 2, Abstract of Repair/Replacement Activities Required for Continued

Service

This information is applicable to Inservice Inspection (ISi) activities performed during operating Cycle 29 at Monticello Nuclear Generating Plant (MNGP) Unit 1, including the 29th refueling outage. Cycle 29 began May 14, 2017, immediately following completion of the 28th refueling outage.

Examinations and tests for Cycle 29 were scheduled and conducted in accordance with the following plans:

• 5th Interval ISi Plan, applicable to Inspection Period 2 • 2nd Interval IWE Plan, applicable to Inspection Period 3.

Also included in this repmi is supplemental infonnation for the Cycle 23 ISi Summary Repo1i submitted July 27, 2007 (Reference ADAMS Accession Number ML072110097). MNGP identified a previously undocumented Repair/Replacement activity, entered it into the Quality Issues Management/ Corrective Action Program, and completed the required documentation applicable to the activity, including this supplemental information.

1 NRC Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 18, March 2017.



SECTION 2. FORMOAR-1 Page 1 of 1

FORM OAR-1 OWNER'S ACTIVITY REPORT

Report Number_~M~N~G=P~1 R~2=9~0'-A~R~-1~----------------------------

Plant _ __,_,M=o"-'n~ti"'ce=l=lo-'N...,_u=c""le=a"-'-r-'G=e=n=e"'ra""'t"'"in=q.._,P-'l=a"'nt,,_, =2.,,_80""'7'-'-W~e"'s"-t __,,C'-"o=u'-'-nt'-'y--'R"""o""'a"--"d,_7,....,5'-'-,-"M'-"o"'"n""ti"'c"'"el,,_,lo'-'-, _,_,M"-'i"'n n"'e""'s"'o'-"ta"-----"5"'5"""'3,,,_62==-----------

Unit No. ------''-----(if applicable)

Commercial service date -~J--'u~n~e-3__,0~1~97~1~_ Refueling outage no. __ ~1~R~2~9 __ _

Current inspection interval -~IS~I~: ~5_th--'l~ns~p--'e__,c=tio=n~ln~te=rv~al~~-~IW~E~: ~2=n-d ~ln=s=p=ec=t=io~n__,l~nt=e~rv~a~I __________ _ (1st, 2nd, 3rd, 4th, other)

Current inspection period --=IS""'I,_: -=2~nd-'l'-'-n=sp=e"-'c,_,,ti-=-o"-n ~P_,,e=ri-=-od-"------''---=IW__,_E=--: -=-3_rd"""I n""'s""p"'e"'c"'tio=n-'--'--P-"-er'""io""'de__ __________ _ (1st, 2nd, 3rd)

Edition and addenda of Section XI applicable to the inspection plans ISi: 2007 Ed, 2008 Add / IWE: 2001 Ed, 2003 Add

Date and revision of inspection plans ISi: 5th Interval Plan, Rev.1, 4/5/2017 / IWE: 2nd Interval Plan, Rev. 2A, 4/19/2019

Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans ____ _

2007 Edition, 2008 Addenda applicable to repair/replacement activities for the IWE 2nd Interval Plan

Code Cases used for inspection and evaluation:_~N~-5=0~8=--"4.....,N--'-~5~5=2--1~N~-=6~13=--"1~N__,-7~0=2~N-'-7~1~6~-----------(it applicable, including cases modified by Case N-532 and later revisions)

CERTIFICATE OF CONFORMANCE

I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the

ASME Code, Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of __ 1'-'-R=2=9~{2=0--'1-"-9~R~FO~l ,---(refueling outage number)

conform to the requirements of Section XI.

Signed:-/ ' ~ . ISi Program Owner Date ___ ~Au.---'----c~rlr-1/16:f~-~-+->-1_0_\_C) ______ _ Owner or Owner's Designee, Tille \J

CERTIFICATE OF INSERVICE INSPECTION

I. the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford, Connecticut have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in the report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

--~---_'>t~A _ __,_4~~f2 __ J,_L--'.vi,~,=-'-1 ____ Commission ----~N=B~1~1-=-8=63~I~N=R~_,_,_M~N,.._0=0~4~0=2-=-8---=C,..,O"---------

Inspector's Signature (National Board Number and Endorsements)

Date __ ;y-_· _/_(,_, _/~l?L___ __ _



SECTION 3. TABLE 1 Page 1 of 1

Examination Category and Item

Number

F-A, F1.10c

F-A, F1 .20c

TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED

EVALUATION FOR CONTINUED SERVICE

Item Description Evaluation Description

Class 1 Piping Support VT-3 identified a drawing non-conformance; locking nuts were not

Support TWH-171, variable spring installed on U-bolt. Determined not to be a service induced condition, and evaluated by engineering for continued service.

support for Residual Heat Removal Reference QIM / CAP AR 501000025520. Subsequently restored (RHR) return piping, Division 2 to design condition, locking nuts installed.

Class 2 Piping Support Previously identified, slightly bent rod reaffirmed, previously

Support PSH-116, variable spring evaluated by engineering for continued service. Reference CAP AR 01558248.

support for High Pressure Coolant Injection (HPCI) steam supply piping. Loose eye rod to spring can locking nut, both spring cans.

Reference QIM / CAP AR's 501000026320 and 501000026821. Evaluated by engineering for continued service. Subsequently restored to design condition, locking nuts tightened.

South spring can, eye rod threaded too far into spring can, in contact or near contact with lower spring compression rod. Evaluated by engineering for continued service. Reference QIM / CAP AR and 501000026821. Subsequently restored to design condition, eye rod installation condition corrected.

QIM / CAP AR - acronyms for "Quality Issue Management I Corrective Action Program - Action Request"


SECTION 4. TABLE2

TABLE 2


Page 1 of 1

ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE

Item Description Date Repair/Replacement Code Class Description ofWork Completed Plan Number

3 Emergency Filtration Replacement of 5/1/2019 2017-29-005, Rev. 2 Train - Emergency piping due to MIC Service Water, pilling with Division 1 remaining wall ESW1-3"-HBD, supply thickness less than piping required minimum

wall. Reference QIM/CAPAR 501000028239.

3 Emergency Service Replacement of 4/25/2019 2019-29-037 Water, Division 2 piping elbow due to ESW5-4"-HBD, supply through wall hole piping from MIC.

Reference QIM / CAP AR 501000026135.

QIM / CAP AR - acronyms for "Quality Issue Management/ Corrective Action Program - Action Request"

MIC - Microbiologically Induced Corrosion


SECTIONS.


Cycle 23 ISi Summary Report Supplemental Information

(6 pages to follow)

Supplemental records, applicable to the Cycle 23 ISI Summary Report, include the following items:

1. Summary Repo1i Section II, "F mm NIS-1 Information" • Updated "Form NIS-1, Owner's Data Repmi for Inservice Inspections," pages

1 of2 and 2 of 2

2. Summary Repmi Section III, "Form NIS-2 Infmmation" • Updated "Cycle 23 NIS-2 Summary," page 5 of 5 • Updated "NIS-2 Forms" leader page • "Form NIS-2 Owner's Repmi for Repair/Replacement Activity," pages 1 of 2

and 2 of2 o Applicable to Repair/Replacement Plan 2018-23-0072 for High Pressure

Coolant Injection (HPCI) valves HPCI-65 and HPCI-71.

Note: The heading on the following pages is applicable to the Cycle 23, 2007 Refueling Outage Summary Report.

Supplemental Record - Updated July 30, 2019 Reference Monticello Quality Issue/ Corrective Action (QIM/CAP) 501000013190

Nuclear Management Company Monticello Inservice Inspection


II. Form NIS-1 Information

1. Owner:

Form NIS-1 Owner's Data Report for Inservice Inspections As required by the Provisions of the ASME Code Rules

Xcel Energy, LLC / Nuclear Management Company, LLC

Page 1 of2

Address:

2. Plant:

800 Nicollet Mall, Mpls, MN 55402 I 700 1st St., Hudson WI 54016

Monticello Nuclear Generating Plant Address: Monticello, MN 55362

3. Plant Unit: 1 4. Owner (Certificate of Authorization): N/ A

5. Commercial Service Date: 6/30/71 6. National Board No. for Unit: NIA

7. Components Inspected:

Component or Appurtenance

Reactor Pressure Vessel

Manufacturer or Installer

Chicago Bridge &Iron

Manufacturer or Installer State or Serial No. Province No.

B-4697

(See appendices for components inspected during the cycle)

8. Examination Dates: 04/13/05 to 04/28/07 .

9. · Inspection Interval: 05/01/03 to 05/31/12 .

10. Applicable Edition of Section XI: 1995 Addenda: 1996 .

National Board No.

11. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.

• See appendices A through D (Attached)

12. Abstract of Conditions Noted.

• See appendices A through E (Attached)

13. Abstract of Corrective Measures Recommended and Taken.

• See appendices A through E (Attached)




II. Form NIS-1 Information Page 2 of2

We certify that the statements made in this report are correct and the examinations and corrective measures taken confonn to the rules of the ASME Code, Section XI.

Certification of Authorization No. (if applicable) __ N ..... / A _____ Expiration Date _____ N ____ / A _____ _

Date~ 2011_ Signed_'X_c.6_L_l?N_e_:R_&_,_y __ By ')~~ ~ Owner Section XI ISi Coordinator


I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of '"', //Ml' SfJI 1>1 and

d b . , , , , , , _ /.JvrJl(t{<C/✓ <0/'1/\1IW employe yN-11ir~.111 1J J Tt·r,t11Jo1ttf! 11,;Jt,tJ.AMi:: l\lvn o 1J\11.t eoft.JJJ 1 < r have inspected the components described in this Owner's Report during the period

Lt It J /q ~ - to 7 0 u I v, , and state that to the best of my knowledge and belief, the Owner has perfonned examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss.of any kind arising from or connected with this inspection. ·

--·~_~,.._~z"---'-,4_/4_i~.~-lt~v .... l'-",_,. ___ Commissions 1,r/:1 /W6J 1 IV R /'11,/ t.'0ct)l/,)l$'

Inspector's Signature National Board, State, Province, Endorsements

Date Jlfl'-r 'Jo 20/f'/

NOTE: Form NIS-1 revision, July 30, 2019. Revised due to addition of Form NIS-2 for Repair/Replacement Plan 2018-23-0072 applicable to the Cycle 23 ISi Summary Report. Reference Monticello Quality Issue/ Corrective Action (QIM I CAP) 501000013190.

I See Note

I See Note

f. See N.ote

See Note



III. Form NIS-2 Information

R/RITEM WORK NUMBER DOCUMENT(S)

2007-23-0056 WO-322070

2007-23-0057 WO-322070

2007-23-0058 WO-291884

2007-23-0059 WO-291592

2007-23-0060 WO-267369

2007-23-0061 WO-141358

2007-23-0062 WO-291592

2007-23-0063 WO-291883

2007-23-0064 WO-291885

2007-23-0065 WO-322083

2007-23-0066 WO-142056·

2007-23-0067 WO-141016

2007-23-0068 WO-324116

2007-23-0069 WO-323428

2007-23-0070 WO-325774

.. 2007-23-0071 WO-326373

2018-23-0072 WO-323868 / 323869


Page 5 of 5

Cycle 23 NIS-2 Summary

COMPONENT WORK DESCRIPTION OR SYSTEM·

RV-2-7LC Replaced main body with rebuilt spare·

RV-2-7LC Replaced topworks with rebuilt spare

RV-2-71B Replaced 5 bolts and 6 nuts for main body to topworks flange

CV-1729 Replaced valve body.

Drywell Head Replaced 2 bolts and 3 nuts

SS-17A Replaced 4 flange mounting bolts

CV-1729 Replaced plug

RV-2-71E Replace 12 studs and 24 nuts for main body to piping inlet flange

RV-2-71G Replace 12 bolts and 12 nuts for main body to topworks flange

RV-2-71A Replace 12 bolts and 12 nuts for main body to topworks flange

MO-2035 Rep)aced 1 stud and 16 nuts, _and the pressure retaining disc

Replaced approximately 4 ft section of piping and RHRSW removed/ re-installed, by welding, portion of restraint

SR-396

RHRSW . Replaced approximately 4 ft section bf piping

VIS-H3 (PH-28) Replaced slightly bent hanger rod:,

ESWl-4"-HBD Replaced approximately 6" section of pipe and <1djaceilt 90 degree elbow

ESWS-4"-HBD Replaced 90 degree elbow

HPCl-65 / HPCl-71 Replaced valve center section (body/ poppet)

NOTE: Form NIS-1 revision, July 30, 2019. Revised due to addition of Form NIS-2 for Repair/Replacement Plan 2018-23-0072 applicable to the Cycle 23 ISi Summary Report. Reference Monticello Quality Issue/ Corrective Action (QIM / CAP) 501000013190.

I See Note



ID. Form NIS-2 Information

NIS-2 Forms

( 14 2 pages to follow)


NOTE: Form NIS-1 revision, July 30, 2019. Revised due to addition of Form NIS-2 for Repair/Replacement Plan 2018-23-0072 applicable to the Cycle 23 ISi Summary Report. Reference Monticello Quality Issue/ Corrective Action (QIM / CAP) 501000013190.

I See Note


MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5

REPAIR/REPLACEMENT ACTIVITY Page 1 of 2

Repair/Replacement Plan No.:2018-23-0072 -----------

1. Owner NSP-Minnesota, an Xcel Energy Company Name

414 Nicollet Mall, Minneapolis, MN 55401 Address

2. Plant Monticello Nuclear Generating Plant Name

2807 West County Road 75, Monticello, MN 55362 Address

3. Work Performed By NMC I Xcel Energy Company Name

2807 W Cty Rd 75, Monticello, MN 55362 Address

Date 612912018

Sheet 1 of 2 ------- ------Unit 1 ---------------

WO's 323868 and 323869 Repair Organization P.O. No., Job No. etc.

Type Code Symbol Stamp NIA -------Authorization No. NIA ----------Expiration Date NIA -----------

4. Identification of System High Pressure Coolant Injection valves HPCl-65 and HPCl-71, Class 2

5. (a) Applicable Construction Code ANSI 831.1 , 1977/W'1978 Edition I Addenda -----------(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda

(c) Applicable Section XI Code Case(s) NIA ----------------------6. Identification of Components

Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stamped

Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO

HPC/-65 BNL 8990902-5-1 NIA N32 2000 Removed • igJ

HPCl-65 BNL B990902-6-1 NIA N32 2007 Installed • igJ

HPCl-71 BNL B990902-5-2 NIA N32 2000 Removed • igJ

HPCl-71 BNL B990902-6-2 NIA N32 2007 Installed • igJ

• • 7. Description of Work Removed center section (body/poppet) and replaced as part of PM activity.

8. Tests Conducted: Hydrostatic D Other D

Pneumatic D Nominal Operating Pressure ~

Exempt D Pressure *970120 psi TestTemp NIA °F

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is

M/asc

8-1/2 in x 11 in, (2) information in items 1 through 6 on this report Is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. (See 4 AWl-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance,)

Approval: PCR 01148046


MONTICELLO NUCLEAR GENERA TING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5

REPAIR/REPLACEMENT ACTIVITY Page 2 of 2

Repair/Replacement Plan No.: 2018-23-0072 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

/ST open and close test per 0255-06-/A-8. Appendix J, LLRT test per 0137-09. System leakage test with VT-2 per 0255-06-//C-1 (2009 RFO). *970 psi at HPCI Turbine inlet, 20 psi at HPCI Turbine Exhaust. Reference CAP QIM-501000013190.

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section XI.

Signed I- e~a- 'I. S J.. Y~IY'- OwJ.Je ~ Date Owner or Owner's Designee, Title


I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by Hartford Steam Boiler lnsp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 'l-/l//2.007 to to/VI/ 2.ota , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in the Owner's Report. Furthermore, neither the Inspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

/ _A_~_-_~-_t_.~---~--~------ Commissions /v/J//.f:/, .3 /VJ, ;fl. /1/(/ CO- Ov,fdZ<j-lnspector's Signature National Board, Province and Endorsements

Date

M/asc

ENCLOSURE 2

Monticello Nuclear Generating Plant

IVVI Steam Dryer Inspection Results (RF029)

RF029 Steam Dryer Inspection Summary Report

The Monticello replacement steam dryer (RSD) was inspected in accordance with the inspection recommendations described in L TR-A&SA-12-8, Rev 1, Westinghouse Recommendations for the Monticello Replacement Steam Dryer Inspections, which was submitted to the NRG in letter L-MT-12-090 dated October 22, 2012. The examinations and the results are detailed in Table 1.

Nine (9) weld locations were inaccessible for inspection or no weld was identified. The weld locations that were inaccessible for inspection are italicized in Table 1. One location was identified having relevant indications and was evaluated to be acceptable for the next two refueling cycles prior to the next visual examination (L TR-PCBE-19-11, Engineering Evaluation 608000000414).

The examinations were performed using both VT-3 and VT-1-89 visual inspection techniques. VT-1-89 is a visual examination using VT-1 resolution, distance, and angle of view requirements described in ASME Section XI, Subparagraph IWA-2211(b), 1989 Edition, No Addenda. VT-1-89 is the recommended technique for steam dryer inspections and should be used to the extent practical per BWRVIP-139-R1-A, Steam Dryer Inspection and Flaw Evaluation Guidelines. LTR-A&SA-12-8, Rev 1 notes that the general guidelines for the inspections should be based on the general principles found in BWRVIP-139-R1-A.

Page 1 of 6

Weld Name

RSD-INT-GEN RSD-OUT-0°-90°

RSD-OUT-90°-180° RSD-OUT-180°-270° RSD-OUT-270° -360°

RSD-SR-VLSl-35 ° RSD-SR-VLSl-145° RSD-SR-VLSl-215° RSD-SR-VLSl-325°

RSD-LS-35° RSD-LS-145° RSD-LS-215° RSD-LS-325° RSD-A1-V2a RSD-A1-V2b RSD-B1-V2a RSD-B1-V2b RSD-C1-V2a RSD-C1-V2b RSD-A2-H1 RSD-A2-H2 RSD-A2-V1 RSD-A3-H1 RSD-A3-H2 RSD-A3-V1 RSD-A4-V1 RSD-A6-H1 RSD-A6-H2 RSD-A6-V1 RSD-A7-H1 RSD-A7-H2 RSD-A7-V1

RF029 Steam Dryer Inspection Summary Report Attachment 1: Steam Dryer Figures

Table 1: RFO29 Monticello Replacement Steam Dryer Inspection Results

Weld Description Exam Exam Result Type

Replacement Steam Dryer Interior VT-3 No relevant indications. Replacement Steam Dryer Outside 0° -90° VT-3 No relevant indications.

Replacement Steam Drver Outside 90° -180° VT-3 No relevant indications. Replacement Steam Dryer Outside 180° -270° VT-3 No relevant indications. Replacement Steam Drver Outside 270° -360° VT-3 No relevant indications.

Support Ring Vessel Lug Interface at 35° VT-3 No relevant indications. Support Rinq Vessel Luq Interface at 145° VT-3 No relevant indications. Support Ring Vessel Lug Interface at 215° VT-3 No relevant indications. Support Rinq Ves.sel Lug Interface at 325° VT-3 No relevant indications.

Levelinq Screw at 35° VT-3 No relevant indications. Leveling Screw at 145° VT-3 No relevant indications. Levelinq Screw at 215° VT-3 No relevant indications. Leveling Screw at 325° VT-3 No relevant indications.

Vane Bank A 1 Right Vertical Weld VT-1-89 No relevant indications. Vane Bank A 1 Left Vertical Weld VT-1-89 No relevant indications.

Vane Bank B1 Riqht Vertical Weld VT-1-89 No relevant indications. Vane Bank B1 Left Vertical Weld VT-1-89 No relevant indications.

Vane Bank C1 Right Vertical Weld VT-1-89 No relevant indications. Vane Bank C1 Left Vertical Weld VT-1-89 No relevant indications. Hood A2 Bottom Horizontal Weld VT-1-89 No relevant indications.

Hood A2 Top Horizontal Weld VT-1-89 No relevant indications. Hood A2 Right Vertical Weld VT-1-89 No relevant indications.

Hood A3 Bottom Horizontal Weld VT-1-89 No relevant indications. Hood A3 Top Horizontal Weld VT-1-89 No relevant indications. Hood A3 Right Vertical Weld VT-1-89 No relevant indications. Hood A4 Right Vertical Weld VT-1-89 No relevant indications.

Hood A6 Bottom Horizontal Weld VT-1-89 No relevant indications. Hood A6 Top Horizontal Weld VT-1-89 No relevant indications. Hood A6 Riqht Vertical Weld VT-1-89 No relevant indications.

Hood A7 Bottom Horizontal Weld VT-1-89 No relevant indications. Hood A7 Top Horizontal Weld VT-1-89 No relevant indications. Hood A7 Right Vertical Weld VT-1-89 No relevant indications.

---------------------------···---·•--·--•··

Page 2 of 6

RSD-A8-V1 RSD-B6-H1 RSD-B6-H2 RSD-B6-V1 RSD-B7-V1 RSD-C8-H1 RSD-C8-H2 RSD-C8-V1 RSD-C1-V1

RSD-A6-UG-H1 RSD-A6-UG-H2 RSD-B6-UG-H1 RSD-86-UG-H2 RSD-C6-UG-H1 RSD-C6-UG-H2

RSD-EB-35° RSD-EB-145° RSD-EB-215° RSD-EB-325°

RSD-GRS-SP-V1-0° RSD-GRS-SP-V1-180° RSD-GRS-SP-V2-0°

RSD-GRS-SP-V2-180° RSD-Hub-PP

RSD-Hub-UG6 RSD-Hub-UG7

RSD-ID-LG4-ICP-3 RSD-ID-LG3-ICP-3 RSD-ID-A1-T-VB RSD-ID-B.1-T-VB RSD-ID-C1-T-VB RSD-/D-A 1-V1a RSD-ID-A1-V1b RSD-ID-B1-V1 a RSD-ID-B1-V1 b RSD-ID-C1-V1a


Hood AS Right Vertical Weld VT-1-89 No relevant indications. Hood 86 Bottom Horizontal Weld VT-1-89 No relevant indications.

Hood 86 Top Horizontal Weld VT-1-89 No relevant indications. Hood 86 Riqht Vertical Weld VT-1-89 No relevant indications. Hood 87 RiQht Vertical Weld VT-1-89 No relevant indications:

Hood CS Bottom Horizontal Weld VT-1-89 No relevant indications. Hood CS Top Horizontal Weld VT-1-89 No relevant indications. Hood CS Right Vertical Weld VT-1-89 No relevant indications. Hood C1 Riqht Vertical Weld VT-1-89 No relevant indications.

Upper Girder to Vane Bank Weld VT-1-89 No relevant indications. Upper Girder to Vane Bank Weld VT-1-89 No relevant indications. Upper Girder to Vane Bank Weld VT-1-89 No relevant indications. Upper Girder to Vane Bank Weld VT-1-89 No relevant indications. Upper Girder to Vane Bank Weld VT-1-89 No relevant indications. Upper Girder to Vane Bank Weld VT-1-89 No relevant indications.

Earthquake Bracket at 35° VT-3 No relevant indications. Earthquake Bracket at 145° VT-3 No relevant indications. Earthquake Bracket at 215° VT-3 No relevant indications. Earthquake Bracket at 325° VT-3 No relevant indications.

Guide Rod Slot to Skirt Panel Weld at 0° VT-1-89 No relevant indications. Guide Rod Slot to Skirt Panel Weld at 180° VT-1-89 No relevant indications.

Guide Rod Slot to Skirt Panel Weld at 0° VT-1-89 No relevant indications. Guide Rod Slot to Skirt Panel Weld at 180° VT-1-89 No relevant indications.

Hub to Perforated Plate Weld VT-1-89 No relevant indications. Hub to Upper Girder Weld VT-1-89 No relevant indications. Hub to Upper Girder Weld VT-1-89 No relevant indications.

Lower Girder to Inner Cover Plate Weld VT-1-89 a No relevant indications Lower Girder to Inner Cover Plate Weld VT-1-89 No relevant indications

Trouqh to Vane Bank Weld VT-1-89 No relevant indications TrouQh to Vane Bank Weld VT-1-89 No relevant indications Trough to Vane Bank Weld VT-1-89 No relevant indications Vertical Outer Plate Weld VT-1-89 Weld is inaccessible for inspection. Vertical Outer Plate Weld VT-1-89 Weld is inaccessible for inspection. Vertical Outer Plate Weld VT-1-89 No relevant indications Vertical Outer Plate Weld VT-1-89 No relevant indications Vertical Outer Plate Weld VT-1-89 No relevant indications

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RSD-ID-C1-V1 b RSD-I D-A3-LG3-T2 RSD-ID-A3-LG4-T1 RSD-ID-B3-LG3-T2 RSD-I D-B3-LG4-T1 RSD-ID-C3-LG3-T2 RSD-I D-C3-LG4-T1

RSD-ID-B1-S1 RSD-ID-B1-S2 RSD-ID-B2-S1 RSD-ID-B2-S2 RSD-ID-B3-S1 RSD-ID-B3-S2 RSD-ID-B4-S1 RSD-ID-B4-S2 RSD-ID-B5-S1 RSD-ID-B5-S2 RSD-ID-B6-S1 RSD-ID-B6-S1 RSD-ID-B7-S1 RSD-ID-B7-S1 RSD-ID-B8-S1 RSD-ID-B8-S1 RSD-I D-C1-S1

RSD-ID-C2-S2 RSD-ID-C3-S1 RSD-ID-C4-S2 RSD-ID-C5-S1 RSD-ID-C6-S2 RSD-ID-C7-S1 RSD-ID-C8-S1

RSD-LR-BRKT-35° RS.D-LR-BRKT-145° RSD-LR-BRKT-215° RSD-LR-BRKT-325°

RSD-LR-LE-35°


Vertical Outer Plate Weld VT-1-89 No relevant indications Trouqh to Lower Girder Weld VT-1-89 No relevant indications Trough to Lower Girder Weld VT-1-89 No relevant indications Trouqh to Lower Girder Weld VT-1-89 No relevant indications Trough to Lower Girder Weld VT-1-89 No relevant indications Trouqh to Lower Girder Weld VT-1-89 No relevant indications Trough to Lower Girder Weld VT-1-89 No relevant indications

Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications· Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 Relevant Indications

Evaluated under MOC 608000000414 Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications Stiffener Welds VT-1-89 No relevant indications

Liftinq Rod Bracket at 35° VT-1-89 No relevant indications Liftinq Rod Bracket at 145° VT-1-89 No relevant indications Liftinq Rod Bracket at 215° VT-1-89 No relevant indications Lifting Rod Bracket at 325° VT-1-89 No relevant indications

Liftinf! Eye to Rod Weld at 35° VT-1-89 No weld identified in this location.

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RSO-LR-LE-145° RSO-LR-LE-215° RSO-LR-LE-325° RSD-LR-SR-35°

RSD-LR-SR-145° RSD-LR-SR-215° RSD-LR-SR-325° RSD-SFW-0°-90°

RSD-SFW-90°-180° RSD-SFW-180°-270° RSD-SFW-270°-360° RSD-SR-SP-0°-90°

RSD-SR-SP-90°-180° RSD-SR-SP-180°-270? RSD-SR-SP-270°-360°

RSD-SRCP-35°-90° RSD-SRCP-90°-145°

RSD-SRCP-215°-270° RSD-SRCP-270°-325:

RSD-UG6-OB RSD-UG7-OB

RSD-1 D-DC3-V1 RSD-1 D-DC4-V1 RSD-ID-DC7-V1 RSD-ID-DC8-V1 RSD-ID-DC2-V2 RSD-ID-DC3-V2 RS D-1 D-DC6-V2 RSD-ID-DC7-V2 RSD-ID-LG3-LR RSD-ID-LG4-LR RSD-ID-ICP-C3 RSD-1 D-LR-CCP RSD-ID-LR-ICP-3 RSD-ID-LG-DC1 RSD-1 D-LG-DC2


Lifting Eye to Rod Weld at 145° VT-1-89 No weld identified in this location. Lifting Eye to Rod Weld at 215° VT-1-89 No weld identified in this location. Lifting Eye to Rod Weld at 325° VT-1-89 No weld identified in this location.

Liftinq Rod to Support Rinq Weld at 35° VT-1-89 No relevant indications Lifting Rod to Support Ring Weld at 145° VT-1-89 No relevant indications Lifting Rod to Support Ring Weld at215° VT-1-89 No relevant indications Lifting Rod to Support Ring Weld at 325° VT-1-89 No relevant indications

Skirt to Flange Weld from 0° -90° VT-1-89 No relevant indications Skirt to Flange Weld from 90° -180° VT-1-89 No relevant indications

. Skirt to Flanqe Weld from 180° -270° VT-1-89 No relevant indications Skirt to Flange Weld from 270° -360° VT-1-89 No relevant indications

Support Ring to Skirt Panel Weld from 0°-90° VT-1-89 No relevant indications Support Ring to Skirt Panel Weld from 90°-180° VT-1-89 No relevant indications

Support Rinq to Skirt Panel Weld from 180° -270° VT-1-89 No relevant indications Support Ring to Skirt Panel Weld from 270°-360° VT-1-89 No relevant indications

Support Rinq Cover Plate Weld from 35°-90° VT-1-89 No relevant indications Support Ring Cover Plate Weld from 90°-145° VT-1-89 No relevant indications

Support Rinq Cover Plate Weld from 215°-270° VT-1-89 No relevant indications Support Ring Cover Plate Weld from 270°-325° VT-1-89 No relevant indications

Upper Girder to Octagonal Beam Weld VT-1-89 No relevant indications Upper Girder to Octagonal Beam Weld VT-1-89 No relevant indications

Skirt to Drain Channel Weld - Left Side of Weld VT-1-89 No relevant indications Skirt to Drain Channel Weld - Left Side of Weld VT-1-89 No relevant indications Skirt to Drain Channel Weld - Left Side of Weld VT-1-89 No relevant indications Skirt to Drain Channel Weld - Left Side of Weld VT-1-89 No relevant indications Skirt to Drain Channel Weld - Right Side of Weld VT-1-89 No relevant indications Skirt to Drain Channel Weld - Right Side of Weld VT-1-89 No relevant indications Skirt to Drain Channel Weld - Right Side of Weld VT-1-89 No relevant indications Skirt to Drain Channel Weld - Riqht Side of Weld VT-1-89 No relevant indications

Lower Girder to Lower Ring Weld VT-1-89 No relevant indications Lower Girder to Lower Ring Weld VT-1-89 No relevant indications Inner Cover Plate to Trough Weld VT-1-89 No relevant indications

Lower Ring to Center Cover Plate Weld VT-1-89 No relevant indications Lower Rinq to Inner Cover Plate Weld VT-1-89 No relevant indications Lower Girder to Drain Channel Weld VT-1-89 No relevant indications Lower Girder to Drain Channel Weld VT-1-89 No relevant indications

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RSD-I D-LG-DC3 RSD-ID-LG-DC4 RSD-ID-LG-DC5 RSD-ID-LG-DC6 RSD-ID-LG-DC7 RSD-ID-LG-DC8

RSD-A1-H3 RSD-B1-H3 RSD-C1-H3


Lower Girder to Drain Channel Weld VT-1-89 No relevant indications Lower Girder to Drain Channel Weld VT-1-89 No relevant indications Lower Girder to Drain Channel Weld VT-1-89 No relevant indications Lower Girder to Drain Channel Weld VT-1-89 No relevant indications Lower Girder to Drain Channel Weld VT-1-89 No relevant indications Lower Girder to Drain Channel Weld VT-1-89 No relevant indications

Hood Vane Bank Top Plate to Perforated Plate VT-1-89 Weld inaccessible for inspection Hood Vane Bank Top Plate to Perforated Plate VT-1-89 Weld inaccessible for inspection Hood Vane Bank Top Plate to Perforated Plate VT-1-89 Weld inaccessible for inspection

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